02149nam 2200457I 450 991070569680332120231213001351.0(CKB)5470000002451424(OCoLC)984992909(EXLCZ)99547000000245142420170501j200405 ua 0engur|||||||||||txtrdacontentcrdamediacrrdacarrierCFD analysis of full-scale steam generator inlet plenum mixing during a PWR severe accident /C.F. Boyd, D.M. Helton, K. HardestyWashington, DC :Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,May 2004.1 online resource (xi, 72 pages) illustrations"Publisher appears on title page as: Division of Systems Analysis and Regulatory Effevtiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.""NUREG-1788.""Manuscript completed: May 2004; date published: May 2004."Includes bibliographical references.CFD analysis of full scale steam generator inlet plenum mixing during a PWR severe accidentComputational fluid dynamics analysis of full-scale steam generator inlet plenum mixing during a pressurized-water reactor severe accidentPressurized water reactorsAccidentsNuclear reactor accidentsNuclear power plantsSafety measuresPressurized water reactorsAccidents.Nuclear reactor accidents.Nuclear power plantsSafety measures.Boyd Christopher Fred1393894Helton D. M.Hardesty K.U.S. Nuclear Regulatory Commission.Division of Systems Analysis and Regulatory Effectiveness,GPOGPOBOOK9910705696803321CFD analysis of full-scale steam generator inlet plenum mixing during a PWR severe accident3453050UNINA